05000328/LER-2005-001, Regarding Unit 2 Reactor Trip Following Closure of Main Feedwater Upon Inadvertent Opening of Control Breakers
| ML051150480 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-079) |
| Issue date: | 04/25/2005 |
| From: | Pace P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 05-001-00 | |
| Download: ML051150480 (8) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3282005001R00 - NRC Website | |
text
April 25, 2005 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT (SQN)
UNIT 2 - DOCKET NO. 50-328 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-328/2005-001-00 The enclosed LER provides details concerning the Unit 2 reactor trip and engineered safety feature (ESF) actuation of auxiliary feedwater. The automatic reactor trip occurred as a result of low-low steam generator level when the main feedwater regulation valves closed upon inadvertent loss of control power. This event is being reported, in accordance with 10 CFR 50.73(a)(2)(iv)(A), as an event that resulted in an automatic actuation of the reactor protection system and ESF actuation.
Sincerely, Original signed by P. L. Pace Manager, Site Licensing and Industry Affairs Enclosure cc (Enclosure):
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway, SE, Suite 100 Atlanta, Georgia 30339-5957
U.S. Nuclear Regulatory Commission Page 2 April 25, 2005 PLP:JDS:ZTK:KTS cc (Enclosure):
A. H. Bhatnagar, LP 6A-C P. M. Billingsley, OPS-4C-SQN (For Web posting)
R. J. Bruno, STC 2H-SQN J. R. Douet, OPS 4A-SQN J. L. Hamilton, OPS 4G-SQN (Attn: R. N. McKaig)
D. F. Helms, LP 6A-C G. M. Holton, BR 3H-C T. A. Keys, BR 6A-C D. A. Kulisek, POB 2B-SQN W. C. Ludwig, OPS 4C-SQN F. C. Mashburn, BR 4X-C T. J. Niessen, OPS 4A-SQN NRC Resident Inspector, OGH-1A-SQN NSRB Support, LP 5M-C K. W. Singer, LP 6A-C E. J. Vigluicci, ET 10A-K EDMS, WT CA-K I:\\license\\lers\\2005 lers\\ler 2-2005-001.doc
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-2004)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Sequoyah Nuclear Plant (SQN) Unit 2
- 2. DOCKET NUMBER 05000328
- 3. PAGE 1 OF 6
- 4. TITLE Unit 2 Reactor Trip Following Closure of Main Feedwater Upon Inadvertent Opening of Control Breakers
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 02 23 2005 2005 - 001 -
00 04 25 2005 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE 1
- 10. POWER LEVEL 100
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) electrical systems; contingency requirement if the proximity of other equipment poses a risk; and a graduated level of reviews up to a review by senior management.
The maintenance procedure for work on molded case breakers has been revised to include positive position control of all panel covers.
VII.
ADDITIONAL INFORMATION
A.
Failed Components:
None B.
Previous LERs on Similar Events:
A review of previous reportable events for the past three years did not identify any
previous similar events
C.
Additional Information
None D.
Safety System Functional Failure:
This event did not result in a safety system functional failure in accordance with 10 CFR 50.73(a)(2)(v).
E.
Loss of Normal Heat Removal Consideration This event did result in a loss of normal heat removal because the closure of the main feedwater regulation valves precipitated the reactor trip.
VIII.
COMMITMENTS
None.